iaea/jaea international workshop · pdf fileprogram director for fuel cycle technologies and...

IAEA/JAEA International ConferenceB. Boullis – Tokai-Mura, november 13th, 2007

IAEA/JAEA INTERNATIONAL WORKSHOPTOKAI-MURA, november 2007

NUCLEAR ENERGY IN THE 21th CENTURY:MAIN TRENDS AND POSSIBLE SCENARIOS IN FRANCE

Bernard BOULLISProgram Director for fuel cycle technologies and waste management

CEA, Nuclear Energy Division


NUCLEAR POWER PLANTS in FRANCE• 34 900 MWe units• 20 1300 MWe units• 4 1500 MWe units

GRAVELINES

CHOOZ

CATTENOMNOGENT / SEINE

ST-LAURENT

CHINONCIVAUX

LE BLAYAIS

GOLFECH

CRUAS

TRICASTIN

ST-ALBAN

BUGEY

DAMPIERRE

PENLYPALUEL

FLAMANVILLE

BELLEVILLE

FESSENHEIM

58 units63 GWe installed415 net TWh in 2004

Connection to the grid :– Unit 1 (Fessenheim 1) : 1977– Unit 58 (Civaux 2) : 1999


FRENCH ELECTRICITY

0

100

200

300

400

500 TWh

1950 1960 1970 1980 1990 2000

541

Hydro

Nuclear

Fossil

64

421

57


CO2 RELEASE AND ELECTRICITY GENERATION

Source AIE 2006


NUCLEAR ENERGY IN FRANCE

• 58 LWRs (and PHENIX !)• >75 % ELECTRICITY SUPPLY

• A « CLOSED » FUEL CYCLE :

– UOX SPENT FUEL REPROCESSED

– U RECYCLED ( 2 REACTORS)

– Pu RECYCLED (20 REACTORS) (from 1987)


SPENT FUEL REPROCESSING AND RECYCLING

LA HAGUE

MARCOULE

MELOX PLANT100t/Y (220 fuel assemblies)

>1200t manufactured

UP2-UP3 PLANTSup to 1600t/y (F+others)>20 000 t processed


> 10.000 GLASS CANISTERS

Hulls ( compacted)

180 liters15% FPs oxides


Reactors --> ≈ 420 TWhe/yr(from MOX fuel : 30 to 40 TWhe/yr)

Spent Fuel cooling pools

Reprocessing≈ 850 HMt/yr

• HL Waste :--> glass canisters (120m3)--> hulls canisters (180m3)

• final disposal whenavailable...

MOX Fuel100 HMt/yr

≈ 220 fuel assemblies/yr

Recovered Uranium

UOX fuel fabrication≈ 1000 HMt/year

Uranium≈ 8000 t/year

Enrichment≈ 5,5 MSWU/year

Plutonium40 HMt/yr

enrichment

TODAY FRENCH CLOSED FUEL CYCLETODAY FRENCH CLOSED FUEL CYCLE


The closed fuel cycle strategy, along with reprocessingand MOX recycling, enables today, with existing facilities :

• Reduction / stabilization of spent fuel quantity : 7 UO2 spent fuel → 1 MOX spent fuel

•Vitrification of high level nuclear waste :•a safe and long-lasting confinement, an international standart• a reduced volume: around 1200 m3 today, and up to 5000 m3 in 2030

• Recycling of plutonium and recovered uranium30% Pu is consumed, produces up to 40 TWh/yr (up to 10% production)

• Preservation of long term energy resourcesconcentration of Pu in MOX spent fuel under a reduced volume, leaves open the possibility to reuse Pu in the future

A CONTRIBUTION TO SUSTAINABILITYA CONTRIBUTION TO SUSTAINABILITY


SPENT FUEL INTERIM STORAGESPENT FUEL INTERIM STORAGE

Spent Fuel inventory HMt

0

10000

20000

30000

40000

1997

2000

2003

2006

2009

2012

2015

2018

2021

2024

2027

2030

HMt

total UO2 + MOX SF MOX SF total SF if end reprocessing total SF pool storage capacity NPPs + LH

410TWhe/year :

hyp: end of reprocessing monorecycling in

2004

Avoided by recycling


A FIRST TRACK FOR THE FUTURE:

• RECYCLE PLUTONIUM INTO GEN3 LWRs !

• Necessity to avoid spent fuel accumulationwhen worldwide « nuclear renaissance » is there!

• Today’s technology as an efficient basis,possibly improved by uranium-plutonium co-management(COEX process, no « pure plutonium stream »)


Reactors --> ≈ 420 TWhe/yr(from MOX fuel : 30 to 40 TWhe/yr)

Spent Fuel cooling pools

Reprocessing≈ 850 HMt/yr

• HL Waste :--> glass canisters (120m3)--> hulls canisters (180m3)

• final disposal whenavailable...

MOX FuelMelox ≈ 100 HMt/yr≈ 220 fuel assemblies/yr

Recovered Uranium

UOX fuel fabrication≈ 1000 HMt/year

Uranium≈ 8000 t/year

Enrichment≈ 5,5 MSWU/year

Plutonium40 HMt/yr

enrichment

TODAY FRENCH CLOSED FUEL CYCLETODAY FRENCH CLOSED FUEL CYCLE


HALL WASTE : THE 1991 FRENCH ACT

• 3 RESEARCH THEMATICS :

– partitionning & transmutation of LLRNs ;

– deep repository ;

– confinment & interim storage.

• 2006 : a public debate, and a new bill

30, december, 1991


THE 2006 FRENCH ACT

ENOUNCES PRINCIPLES :

– RECYCLE (reprocess)to decrease waste amount & toxicity

– RETRIEVABLE GEOLOGICAL REPOSITORYthe reference option for ultimate wastemanagement.

28, june, 2006


THE 2006 FRENCH ACT …

PRECISES A « ROADMAP » :

– 2012 : assess the industrial potentialitiesof diverse P&T options(prototype by 2020)

– 2015 : repository defined(operation by 2025)

28, june, 2006


PRESENTATION OF THE 2006 FRENCH ACT

“With this text, the Government doesn’t propose to you a definitive

solution to the question of radwastemanagement; he proposes to take time enough to implement (step by

step) the solution ….”

François LOOS, Minister for IndustryFrench Parliament, 6 april 2006


NUCLEAR ENERGY IN FRANCE: TRENDS FOR THE FUTURE

A « CLOSED FUEL CYCLE » !

– WITH CURRENT GEN II LWRs

– THEN WITH GEN III EPRs


GENERATION III ADVANCED REACTORS

- A new generation of reactorstaking advantage of the large experience acquired in the operation of Gen II plants (LWRs mainly)

- a main objective: new improvements in safetywhile improving economic competitiveness

- Mitigation of severe accident consequence, major goal


FLAMANVILLE 3 : EPR in FRANCE

(site permit april 2007, operation by 2012


Gen III REACTORS FEATURESGenGen III III reactorsreactors suchsuch as EPR as EPR maymay help help to to reducereduce the plutonium the plutonium inventoryinventory

Plutonium annual balance(Kg Pu/year)

REP 900 UO2 : + 200

REP 900 MOX : 0

EPR 100% MOX : - 670

MOXUOXControl rods

EPRREP 900

An enhanced capacityto burn PlutoniumCapacity to load up to 100% MOX Core


(1) COSTS

(2) SAFETY

MAIN CRITERIA FOR FUTURE NUCLEAR SYSTEMS

(3) « SUSTAINABILITY » :. rational use of natural resources. waste minimization. resistance vs. proliferation risks




– WITH CURRENT GEN II LWRs

– THEN WITH GEN III EPRs (1st Unit, 2012)

– THEN WITH GEN IV FAST REACTORS:• Uranium & plutonium (fuel resource extended)• Americium, Neptunium, Curium ?

(radiotoxicity decreased, …)


FAST REACTORS PROJECTS

60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03595857

RAPSODIE

PHENIX

SUPERPHENIX

EFR

Studies & design Construction DecommissioningOperation

1st criticality

1st connection to the grid Final shutdown

01/67

02/98

08/73 12/73

09/85 01/86

40 MWth

250 MWe

1200 MWe

1500 MWe

10/83

SPX 2

60’s 70’s 80’s 90’s

till 08


FROM GENERATION III TO GENERATION IVLWRs: many advantages,

but can’t satisfy alone sustainability.

Sustainability requires fast neutron systemsto efficiently burn plutonium, and fully use uraniumto reduce efficiently long-term radiotoxicity.

new concepts at industrial maturity :two or three decades(Gen III deployement & operation)

Plutonium stored in spent LWR- MOX fuelscould allow around 2040 the progressive start-up of several fast reactors.


FRENCH PRESIDENT, 6 january, 2006

« …many countries think to the next generation of nuclear reactors, for 2030-2040, which will produceless waste and will use in a better way fissile materials . I decided to launch now the design, by the CEA teams, of a prototype of such a reactor, whichwill be commissionned by 2020.We will cooperate, obviously, with industrial and international partners who would propose to joinus in this project… »




– WITH CURRENT GEN II LWRs(today 22 years old in average)

– THEN WITH GEN III EPRs(1st Unit, 2012 )

– THEN WITH GEN IV FAST REACTORS(transition from 2040?)


AND HYDROGEN GENERATION ?AND HYDROGEN GENERATION ?

Storage

Leak detectionon production

columns

Separationhill

Underground reactor building

Distance

Regulations

(artist view)


Generation 3+

Generation 4Existing fleet40-year plant life

Plant life extension beyond 40 years

0

10000

20000

30000

40000

50000

60000

70000

1975

1980

1985

1990

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

2055

2060

Average plant life : 48 years

Scenario for the renewal of French NPPs

Source : EDF

Inst

alle

d ca

paci

ty (M

We)

60 000

Major role of LWRs over the 21st century


Generation 3+



0

10000

20000

30000

40000

50000

60000

70000

1975

1980

1985

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1995

2000

2005

2010

2015

2020

2025

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2035

2040

2045

2050

2055

2060



Source : EDF

Inst

alle

d ca

paci

ty (M

We)

60 000


EPR, 1st of a kind

Fast reactor Prototype


GUIDELINES FOR THE PROTOTYPE…- SFR, the référence option

- near 600 MWe, loops or pool, ..?.

- increased safety ,competitivity, iso-generation,easier in-service inspection …

-GFR, the main alternative-access to high temperature applications …

-International cooperation, an experimental reactor possibly in Europe (50 MWth)?

-A « challenging » fuel !

-ADS , in the frame of international programs

-


Generation 3+



0

10000

20000

30000

40000

50000

60000

70000

1975

1980

1985

1990

1995

2000

2005

2010

2015

2020

2025

2030

2035

2040

2045

2050

2055

2060



Source : EDF

Inst

alle

d ca

paci

ty (M

We)

60 000


LH plants, 40 years operation


A POSSIBLE SCENARIO IN FRANCE…

Source: EDF - ENC 2002

OperatingFleet

1975 2000 2025 2050 2075

FR

EPR

U (recycled)

Pu (once recycled, MOX fuel)

M.A. + F.P. ---> GlassF.P. ---> Glass

M.A. ---> glass, or recycle

Recycling in FR

Disposal

Gen IVCycle

Lifetimeextension

REACTORS

FUEL CYCLE


WHICH OPTION FOR THE FUTURE ?

R T

U

U PuU & Pu recycled,

COEX

Homogeneousrecycling

R T

U

FP

U Pu AM

R T

U

MAU Pu

FPFP&MA

MA heterogeneousrecycling

R T

U

UU & Pu recycled,

PUREX

Pu

FP&MA R T

U

U Pu

FP

TADS

« double strata »

MA


GENERATION IV FUEL CYCLES

• CRITERIA TO FIT : RESOURCE, WASTE ,PROLIFERATION-RESISTANCE

• SEVERAL OPTIONS,WHICH COULD BE SUCCESSIVELY DEPLOYED

• HETEROGENEOUS, HOMOGENEOUS• AMERICIUM, ALL-ACTINIDE…?

• SOLVENT EXTRACTION,INNOVATIVE TECHNOLOGIES ?


OPTION FOR HETEROGENEOUS MULTI RECYCLE

• core : UPuO2

• “loaded blankets” : UMAO2(MA =Np/Am/Cm)

PuU

MAs

CORE LB


NEW FACILITIES AT LA HAGUE ?

SFR / MOXFUEL

FABRICATION

MINOR ACTINIDES

PILOT( the core of the prototype, tons) (experimental pins,

MONJU demo, kg)


en résumé…TODAY FRENCH LWRs FLEET and CLOSED FUEL CYCLE : an efficient, a mature option

GENIII REACTORS provide in the next decades a new optimization step(with optimized technologies for fuel cycle(COEX ?) it could allow a suitable worldwide restart of nuclear energy, avoiding spent fuel accumulation)

To meet sustainability goals, we need the development of Gen IV systems including fast reactors;

Several fuel cycle options including ,minor actinide recycling ,are still matter of R&D,;

By 2012, CEA (and partners) will present a project for a fast reactor prototype and related fuel cycle facilities, to be operated by 2020


AS A GENERAL RULE …

AT EACH PERIOD OF TIME,TAKE ADVANTAGE OF THE POTENTIALITIES OF THE BEST AVAILABLE TECHNOLOGIES !

GEN III reactors, with appropriate (optimized) technologies for fuel cycle, could allow a suitable worldwide restart of nuclear energy (avoiding spent fuel accumulation), and be used as a “bridge”toward fully sustainable systems

iaea/jaea international workshop · pdf fileprogram director for fuel cycle technologies and...

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